ARIANT Assessments for CANDU Analysis Using RD-14M Experiments

ARIANT (AlgoRIthm for Analysis of Network Thermalhydraulics) is a Canadian Nuclear Laboratories system thermal-hydraulic code for the modeling and analysis of two-phase flow and heat transfer for pressurized heavy water reactors, light water pressurized water reactors, and advanced reactor applications. This paper presents ARIANT models and simulations of RD-14M experiments, including small-break loss-of-coolant accidents, large-break loss-of-coolant accidents, loss-of-flow accidents, station blackout, and natural circulation, that are representative of accident scenarios in a CANDU reactor.

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Publication Details

Journal
Nuclear Science and Engineering
Published
2024-08-19
DOI
https://doi.org/10.1080/00295639.2024.2380628
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
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article

ARIANT Assessments for CANDU Analysis Using RD-14M Experiments

Shujun Wang, Geoffrey Waddington, Songyu Liu, John Cui
Nuclear Science and Engineering
Nuclear reactor physics and engineering
article

ARIANT Assessments for CANDU Analysis Using RD-14M Experiments

Shujun Wang, Geoffrey Waddington, Songyu Liu, John Cui
article en

Abstract

ARIANT (AlgoRIthm for Analysis of Network Thermalhydraulics) is a Canadian Nuclear Laboratories system thermal-hydraulic code for the modeling and analysis of two-phase flow and heat transfer for pressurized heavy water reactors, light water pressurized water reactors, and advanced reactor applications. This paper presents ARIANT models and simulations of RD-14M experiments, including small-break loss-of-coolant accidents, large-break loss-of-coolant accidents, loss-of-flow accidents, station blackout, and natural circulation, that are representative of accident scenarios in a CANDU reactor.

Nuclear Science and EngineeringVol. 199(sup1)
Canadian Nuclear Laboratories (CA)
Climate action
Openalex Percentile: Top 80%
Nuclear reactor physics and engineering
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